US5406601A - Transport and storage cask for spent nuclear fuel - Google Patents
Transport and storage cask for spent nuclear fuel Download PDFInfo
- Publication number
- US5406601A US5406601A US08/236,308 US23630894A US5406601A US 5406601 A US5406601 A US 5406601A US 23630894 A US23630894 A US 23630894A US 5406601 A US5406601 A US 5406601A
- Authority
- US
- United States
- Prior art keywords
- basket
- cask
- cask body
- plates
- open end
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
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-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
- G21F5/008—Containers for fuel elements
Definitions
- the invention is generally related to the transport and storage of radioactive material and particularly to a cask that can be used for transporting or storing spent nuclear fuel.
- Nuclear reactors require periodic replacement of the nuclear fuel. Fuel removed from reactors in naval vessels and some land based commercial reactors must be transported to a storage site. In some instances, there may be storage room at the site of the land based reactor.
- the United States Nuclear Regulatory Commission sets standards that must be met for casks that are used to transport or store spent nuclear fuel. Due to the different conditions that may be encountered during transport and static storage, separate standards are set for transport casks and for storage casks. These standards are respectively set forth in 10 CFR 71 and 10 CFR 72. Shipping casks must be able to withstand shock loads during transport while storage casks must be able to withstand temperature transients such as a fire external to the cask without transmitting additional heat to the inside of the cask.
- the present invention addresses the above problem in a straightforward manner.
- a cask that can be used for both transport and storage of spent nuclear fuel.
- the cask body and basket are designed such that there is a gap between the cask body and basket.
- the basket is formed from multiple layers of rowed plates that cooperate with the cask body to provide the required radiation shielding, thermal, and structural requirements of 10 CFR 71 and 10 CFR 72.
- the plates have complementary shapes and partial hex grooves machined therein such that complete channels for the fuel cells are formed when the plates are mated for insertion into the cask body.
- the plates have narrowed diameter sections and are held together by bands around the circumference of the plates at these sections.
- Locating keys received in grooves between the plates extend the entire axial length of the basket to hold the plates in alignment during assembly and to block radiation leakage across the vertical gaps between the plates.
- Centering keys are provided at the upper and lower ends of the basket and cask body to provide a consistent gap between the basket and cask body. The gap expands during a fire due to thermal expansion of the cask body prior to thermal expansion of the basket and thus does not allow conduction of the external heat into the basket and fuel during an external transient temperature rise.
- FIG. 1 is a longitudinal section view of the invention.
- FIG. 2 is a perspective view of the basket of the invention.
- Transport and storage cask 10 is generally comprised of cask body 12, and basket 14.
- Cask body 12 is formed from stainless steel in the preferred embodiment. As seen in FIG. 1, cask body 12 is closed at one end and provided with suitable shield and seal means at the opposite end. The interior diameter of the upper end of cask body 12 is slightly larger than the remainder of the interior of cask body 12 to receive shield plug 16. This helps to prevent radiation leakage through the upper end. Shear ring segments 18 are positioned on top of shield plug 16 and are received in a notch 20 provided around the inner circumference of cask body 12. Shear ring segments 18 prevent operating and accident loads from being transferred to inner lid 22 which is positioned immediately above shield plug 16. Inner lid 22 is provided with a groove around its lower end necessary to fit around shear ring segments 18.
- Inner lid 22 may be seal welded to the inner circumference of cask body 12 as indicated at numeral 24.
- Outer lid 26 is fastened around its circumference to cask body 12 by bolts or studs 28.
- a replaceable metal O-ring 30 may be placed between outer lid 26 and the end of cask body 12 to provide an outer seal.
- Lifting bales 32 are provided as necessary on the exterior of cask body 12.
- Basket 14 is formed from multiple layers of rowed carbon steel plates 34.
- Plates 34 have complementary shapes and partial hex grooves machined therein such that complete channels 36 for the fuel cells are formed when plates 34 are mated for insertion into cask body 12.
- Channels 36 are illustrated as being hexagonal but may be of any suitable shape depending on the material to be transported or stored.
- Plates 34 have a narrowed diameter 38 at each end and at intervals spaced apart along their length.
- Bands 40 are attached to each other by bolts 41 around plates 34 at each narrowed circumference point 38 to hold plates 34 in their assembled positions.
- the flat mating surfaces of plates 34 are machined to provide a close fit to prevent radiation leakage between plates 34.
- plates 34 may also each be provided with complementary grooves along their length to form a channel 42 between each plate sized to receive a locating key 44 that extends the full length of the plates.
- Each locating key 44 serves the dual purpose of holding the plates in alignment during assembly and blocking radiation from leaking between the mating surfaces at the plate junctions.
- Means for centering basket 14 in cask body 12 to maintain a steady state gap between the interior of cask body 12 and basket 14 are provided on cask body 12 and basket 14 in the form of centering keys 46.
- female key ways are provided at the lower end of basket that are designed to receive male keys on the inside lower end of cask body 12 while male keys are provided at the upper end of basket 14 and female key ways are provided at the upper end of cask body 12.
- the centering keys at the lower end of cask body 12 and basket 14 are preferably sized such that they engage basket 14 during installation in cask body 12 before the centering keys at the upper end engage. This provides for automatic location of the upper centering keys.
- spent nuclear fuel is loaded into fuel cell channels 36 and shield plug 16, inner lid 22, and outer lid 26 are installed. Basket 14 and cask body 12 both undergo thermal expansion due to thermal radiation from the spent fuel that results in the gap between them remaining constant.
- cask body 12 will absorb heat from the fire and undergo thermal expansion.
- little or none of the absorbed heat will be transferred across the gap and the gap will enlarge due to thermal expansion of cask body 12.
- the elevated temperature of cask body 12 from the fire precludes radiation of waste heat from the spent fuel, it has been determined that the peak fuel temperature will not occur until over twelve hours after the onset of the fire transient.
- the present invention thus provides a storage cask for spent nuclear fuel that is capable of withstanding normal operating and accident loads during transportation and normally expected fire transients.
Abstract
Description
Claims (3)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US08/236,308 US5406601A (en) | 1994-05-02 | 1994-05-02 | Transport and storage cask for spent nuclear fuel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US08/236,308 US5406601A (en) | 1994-05-02 | 1994-05-02 | Transport and storage cask for spent nuclear fuel |
Publications (1)
Publication Number | Publication Date |
---|---|
US5406601A true US5406601A (en) | 1995-04-11 |
Family
ID=22888978
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US08/236,308 Expired - Fee Related US5406601A (en) | 1994-05-02 | 1994-05-02 | Transport and storage cask for spent nuclear fuel |
Country Status (1)
Country | Link |
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US (1) | US5406601A (en) |
Cited By (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5633904A (en) * | 1994-11-09 | 1997-05-27 | Newport News Shipbuilding And Dry Dock Company | Spent nuclear fuel (SNF) dry transfer system |
US5898747A (en) * | 1997-05-19 | 1999-04-27 | Singh; Krishna P. | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
US20040011971A1 (en) * | 1996-05-03 | 2004-01-22 | British Nuclear Fuels Plc. | Container for nuclear fuel transportation |
US20050286674A1 (en) * | 2004-06-29 | 2005-12-29 | The Regents Of The University Of California | Composite-wall radiation-shielded cask and method of assembly |
US20060043320A1 (en) * | 1996-05-03 | 2006-03-02 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US20060222139A1 (en) * | 2005-03-29 | 2006-10-05 | Nac International, Inc. | Methods for demonstrating moderator exclusion for nuclear criticality safety |
US20080137794A1 (en) * | 2005-12-01 | 2008-06-12 | Nac International, Inc. | Systems and methods for loading and transferring spent nuclear fuel |
US20090069621A1 (en) * | 2006-10-11 | 2009-03-12 | Singh Krishna P | Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage |
US20090304137A1 (en) * | 2005-08-11 | 2009-12-10 | Tn International | Package Serving to Accommodate a Case Containing Radioactive |
US8995604B2 (en) | 2009-11-05 | 2015-03-31 | Holtec International, Inc. | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
RU167950U1 (en) * | 2016-06-21 | 2017-01-13 | Федеральное государственное унитарное предприятие "Российский федеральный ядерный центр - Всероссийский научно-исследовательский институт технической физики имени академика Е.И. Забабахина" | Container for transporting and / or storage of spent nuclear fuel |
RU2611057C1 (en) * | 2016-03-02 | 2017-02-21 | Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") | Container for storage and transportation of spent fuel assemblies and case for their arrangement |
JP2017078580A (en) * | 2015-10-19 | 2017-04-27 | 株式会社神戸製鋼所 | Radioactive material transportation storage container, and manufacturing method of radioactive material transportation storage container |
WO2020197430A1 (en) * | 2019-03-27 | 2020-10-01 | Акционерное общество "Логистический центр ЯТЦ" (АО "ЛЦ ЯТЦ") | Casing of container for transportation and storage of spent fuel assemblies |
US11342091B2 (en) * | 2004-03-18 | 2022-05-24 | Holtec International | Systems and methods for storing spent nuclear fuel |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3466445A (en) * | 1967-10-06 | 1969-09-09 | Atomic Energy Commission | Container for radioactive fuel elements |
US4292528A (en) * | 1979-06-21 | 1981-09-29 | The Carborundum Company | Cask for radioactive material and method for preventing release of neutrons from radioactive material |
-
1994
- 1994-05-02 US US08/236,308 patent/US5406601A/en not_active Expired - Fee Related
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3466445A (en) * | 1967-10-06 | 1969-09-09 | Atomic Energy Commission | Container for radioactive fuel elements |
US4292528A (en) * | 1979-06-21 | 1981-09-29 | The Carborundum Company | Cask for radioactive material and method for preventing release of neutrons from radioactive material |
Cited By (25)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5633904A (en) * | 1994-11-09 | 1997-05-27 | Newport News Shipbuilding And Dry Dock Company | Spent nuclear fuel (SNF) dry transfer system |
US20110001066A1 (en) * | 1996-05-03 | 2011-01-06 | British Nuclear Fuels Plc, | Container for nuclear fuel transportation |
US20040011971A1 (en) * | 1996-05-03 | 2004-01-22 | British Nuclear Fuels Plc. | Container for nuclear fuel transportation |
US6770897B2 (en) | 1996-05-03 | 2004-08-03 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US6825483B2 (en) | 1996-05-03 | 2004-11-30 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US20060043320A1 (en) * | 1996-05-03 | 2006-03-02 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US8049194B2 (en) | 1996-05-03 | 2011-11-01 | Uranium Asset Management Limited | Container for nuclear fuel transportation |
US5898747A (en) * | 1997-05-19 | 1999-04-27 | Singh; Krishna P. | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
US6064710A (en) * | 1997-05-19 | 2000-05-16 | Singh; Krishna P. | Apparatus suitable for transporting and storing nuclear fuel rods and methods for using the apparatus |
US11342091B2 (en) * | 2004-03-18 | 2022-05-24 | Holtec International | Systems and methods for storing spent nuclear fuel |
US20050286674A1 (en) * | 2004-06-29 | 2005-12-29 | The Regents Of The University Of California | Composite-wall radiation-shielded cask and method of assembly |
US20060222139A1 (en) * | 2005-03-29 | 2006-10-05 | Nac International, Inc. | Methods for demonstrating moderator exclusion for nuclear criticality safety |
US20090304137A1 (en) * | 2005-08-11 | 2009-12-10 | Tn International | Package Serving to Accommodate a Case Containing Radioactive |
US8804895B2 (en) * | 2005-08-11 | 2014-08-12 | Tn International | Cask intended to receive a canister containing radioactive material, and transfer method for said canister |
US20080137794A1 (en) * | 2005-12-01 | 2008-06-12 | Nac International, Inc. | Systems and methods for loading and transferring spent nuclear fuel |
US8067659B2 (en) | 2006-10-11 | 2011-11-29 | Holtec International, Inc. | Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage |
US8415521B2 (en) | 2006-10-11 | 2013-04-09 | Holtec International, Inc. | Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials |
US7994380B2 (en) | 2006-10-11 | 2011-08-09 | Holtec International, Inc. | Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow |
US20090069621A1 (en) * | 2006-10-11 | 2009-03-12 | Singh Krishna P | Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage |
US8995604B2 (en) | 2009-11-05 | 2015-03-31 | Holtec International, Inc. | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
US9208914B2 (en) | 2009-11-05 | 2015-12-08 | Holtec International | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
JP2017078580A (en) * | 2015-10-19 | 2017-04-27 | 株式会社神戸製鋼所 | Radioactive material transportation storage container, and manufacturing method of radioactive material transportation storage container |
RU2611057C1 (en) * | 2016-03-02 | 2017-02-21 | Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") | Container for storage and transportation of spent fuel assemblies and case for their arrangement |
RU167950U1 (en) * | 2016-06-21 | 2017-01-13 | Федеральное государственное унитарное предприятие "Российский федеральный ядерный центр - Всероссийский научно-исследовательский институт технической физики имени академика Е.И. Забабахина" | Container for transporting and / or storage of spent nuclear fuel |
WO2020197430A1 (en) * | 2019-03-27 | 2020-10-01 | Акционерное общество "Логистический центр ЯТЦ" (АО "ЛЦ ЯТЦ") | Casing of container for transportation and storage of spent fuel assemblies |
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AS | Assignment |
Owner name: BABCOCK & WILCOX COMPANY, THE, LOUISIANA Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:HINDERER, JAMEES R.;MENSINK, DANIEL L.;ROLLMAN, THOMAS E.;REEL/FRAME:006988/0663 Effective date: 19940419 |
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Owner name: BWX TECHNOLOGIES, INC., VIRGINIA Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNOR:BABCOCK & WILCOX COMPANY, THE;REEL/FRAME:008829/0402 Effective date: 19970630 |
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Free format text: PATENT EXPIRED DUE TO NONPAYMENT OF MAINTENANCE FEES UNDER 37 CFR 1.362 |
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Effective date: 20030411 |